ML18137A134: Difference between revisions
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| docket = | | docket = | ||
| license number = | | license number = | ||
| contact person = Brady B | | contact person = Brady B, NRR-DMLR 415-2981 | ||
| package number = ML18137A131 | | package number = ML18137A131 | ||
| document type = Meeting Briefing Package/Handouts, Slides and Viewgraphs | | document type = Meeting Briefing Package/Handouts, Slides and Viewgraphs | ||
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=Text= | =Text= | ||
{{#Wiki_filter: | {{#Wiki_filter:NRCs Research Perspectives on Irradiated Concrete Madhumita Sircar US Nuclear Regulatory Commission Office of Nuclear Regulatory Research NEI-EPRI Concrete Workshop Washington, DC May 17, 2018 | ||
*Engagement | |||
*Plant Specific Information | Overview | ||
*Additional Knowledge Development 2 | * Objectives and Outcome | ||
* Engagement | |||
* Plant Specific Information | |||
* Additional Knowledge Development 2 | |||
Research Perspectives | |||
* Reactor pressure vessel (RPV) generally supported under the inlet and/or outlet nozzles | |||
* Nearest load-bearing concrete depends on the nozzle support design | |||
* RPV supported on concrete bioshield (CBS) | |||
* RPV supported on steel columns and horizontal steel frame anchored to CBS for lateral load transfer | |||
* Other safety related concrete structure and components close to RPV Reactor Concepts Manual (ML15252A444) | |||
Research Perspectives Objectives | |||
- Estimation of expected level of radiation (neutron E>0.1 MeV and gamma) on concrete for the period of SLR (up to 80 years of operation) and propagation of radiation through concrete section | |||
- Characterization of degradation due to radiation | |||
- Characterization of concrete damage depth under structural constraints | |||
- Structural significance for long-term operations considering current licensing basis design | |||
- Programmatic aspects for managing the aging effects 4 | |||
Research Perspectives Outcome | |||
- Approaches for confirmatory review of industry research to assess structural performance for the structures exposed to high radiation | |||
- Technical bases to support updating regulatory guidance for structures exposed to high irradiation for operating life up to 80 years (SLR). | |||
5 | |||
Research Perspectives | Research Perspectives | ||
* Engagements | |||
- NRC is conducting confirmatory research | |||
- NRC-DOE-EPRI joint research MOU and roadmap | |||
- NRC-NRA (Japan) bi-lateral research MOU - NRC received experimental data from recently completed NRAJ research | |||
- Participating in International Committee on Irradiated Concrete (ICIC) 6 | |||
Estimated 80-Year Neutron Fluence (E > 0.1 MeV) on Concrete Estimated 80 Year Neutron Fluence (E >0.1 MeV) at Outer RPV (Inner face of concrete is about 10% less). | |||
Source: ORNL/TM-2018/769 7 | |||
Plant-Specific Information to Develop Basic Understanding | |||
- Current neutron fluence and gamma dose information | |||
- Plant configuration and structural details of RPV supports and bioshield wall | |||
- Concrete composition (aggregates, cement, grout, etc.), | |||
reinforcement and supports anchorage | |||
*Engagements | - Environment (temperature and humidity) | ||
-NRC is conducting confirmatory research | - CBS liner and attachment | ||
-NRC-DOE-EPRI joint research MOU and roadmap | - Current Licensing Basis design requirements (method, load combination, design codes) | ||
-NRC-NRA (Japan) bi-lateral research MOU | - Inspection and monitoring methods 8 | ||
-NRC | |||
-Participating in International Committee on Irradiated Concrete (ICIC) 6 Estimated 80 | |||
-Year Neutron Fluence (E > 0.1 MeV) on Concrete | |||
-2018/769 Plant-Specific Information to Develop Basic Understanding | |||
-Current neutron fluence and gamma dose information | |||
-Plant configuration and structural details of RPV supports and bioshield wall | |||
-Concrete composition (aggregates, cement, grout, etc.), reinforcement and | |||
-Current Licensing Basis design requirements (method, load combination, design codes | |||
Plant-Specific Information to Develop Basic Understanding | Plant-Specific Information to Develop Basic Understanding | ||
*Support details | * Support details | ||
*Local design considerations | * Local design considerations - concrete, rebar, anchorages | ||
-concrete, rebar, anchorages | * Characterization of load-resisting mechanisms (for example, steel-concrete bond strength) | ||
*Characterization of load | Source: WCAP-14422 Rev. 2-A | ||
-resisting mechanisms (for example, steel | |||
-concrete bond strength)Source: WCAP | Additional Knowledge Development Irradiated Steel-Concrete Bond Strength [Significant] | ||
-14422 Rev. 2-A Irradiated Steel | - Possible loss of bond due to the irradiation-induced damage of concrete around rebars and support anchorages Rate Effects | ||
-Concrete Bond Strength [Significant] | - Require concrete harvested from decommissioned LWR NPPs | ||
-Possible loss of bond due to the irradiation | * at high dose, i.e., > 1019 n.cm-2 @ E > 0.1 MeV | ||
-induced damage of concrete around rebars and support | * w/ high silica content aggregate No relevant harvesting opportunity as of today. | ||
-Require concrete harvested from decommissioned LWR NPPs | Likely source San Onofre, Keewaunee Examination of In-Situ Damage, Monitoring, and Aging Management approaches Irradiated Concrete Creep | ||
*at high dose, i.e., > | - Need for experimental data. Concrete creep may affect irradiation-induced cracking Irradiation-Assisted Alkali-Silica Reaction | ||
*w/ high silica content aggregate No relevant harvesting opportunity as of today.Likely source San Onofre , | - Irradiation-induced amorphization increases the dissolution rate of aggregates 1 | ||
-Situ Damage, Monitoring, and Aging Management | |||
-Need for experimental data. Concrete creep may affect irradiation | QUESTIONS?}} | ||
-induced | |||
-Assisted Alkali | |||
-Silica Reaction | |||
-Irradiation | |||
-induced amorphization increases the dissolution rate of aggregates |
Latest revision as of 03:54, 21 October 2019
ML18137A134 | |
Person / Time | |
---|---|
Issue date: | 05/17/2018 |
From: | Madhumita Sircar NRC/RES/DE/SGSEB |
To: | |
Brady B, NRR-DMLR 415-2981 | |
Shared Package | |
ML18137A131 | List: |
References | |
Download: ML18137A134 (11) | |
Text
NRCs Research Perspectives on Irradiated Concrete Madhumita Sircar US Nuclear Regulatory Commission Office of Nuclear Regulatory Research NEI-EPRI Concrete Workshop Washington, DC May 17, 2018
Overview
- Objectives and Outcome
- Engagement
- Plant Specific Information
- Additional Knowledge Development 2
Research Perspectives
- Reactor pressure vessel (RPV) generally supported under the inlet and/or outlet nozzles
- Nearest load-bearing concrete depends on the nozzle support design
- Other safety related concrete structure and components close to RPV Reactor Concepts Manual (ML15252A444)
Research Perspectives Objectives
- Estimation of expected level of radiation (neutron E>0.1 MeV and gamma) on concrete for the period of SLR (up to 80 years of operation) and propagation of radiation through concrete section
- Characterization of degradation due to radiation
- Characterization of concrete damage depth under structural constraints
- Structural significance for long-term operations considering current licensing basis design
- Programmatic aspects for managing the aging effects 4
Research Perspectives Outcome
- Approaches for confirmatory review of industry research to assess structural performance for the structures exposed to high radiation
- Technical bases to support updating regulatory guidance for structures exposed to high irradiation for operating life up to 80 years (SLR).
5
Research Perspectives
- Engagements
- NRC is conducting confirmatory research
- NRC-DOE-EPRI joint research MOU and roadmap
- NRC-NRA (Japan) bi-lateral research MOU - NRC received experimental data from recently completed NRAJ research
- Participating in International Committee on Irradiated Concrete (ICIC) 6
Estimated 80-Year Neutron Fluence (E > 0.1 MeV) on Concrete Estimated 80 Year Neutron Fluence (E >0.1 MeV) at Outer RPV (Inner face of concrete is about 10% less).
Source: ORNL/TM-2018/769 7
Plant-Specific Information to Develop Basic Understanding
- Current neutron fluence and gamma dose information
- Plant configuration and structural details of RPV supports and bioshield wall
- Concrete composition (aggregates, cement, grout, etc.),
reinforcement and supports anchorage
- Environment (temperature and humidity)
- CBS liner and attachment
- Current Licensing Basis design requirements (method, load combination, design codes)
- Inspection and monitoring methods 8
Plant-Specific Information to Develop Basic Understanding
- Support details
- Local design considerations - concrete, rebar, anchorages
- Characterization of load-resisting mechanisms (for example, steel-concrete bond strength)
Source: WCAP-14422 Rev. 2-A
Additional Knowledge Development Irradiated Steel-Concrete Bond Strength [Significant]
- Possible loss of bond due to the irradiation-induced damage of concrete around rebars and support anchorages Rate Effects
- Require concrete harvested from decommissioned LWR NPPs
- at high dose, i.e., > 1019 n.cm-2 @ E > 0.1 MeV
- w/ high silica content aggregate No relevant harvesting opportunity as of today.
Likely source San Onofre, Keewaunee Examination of In-Situ Damage, Monitoring, and Aging Management approaches Irradiated Concrete Creep
- Need for experimental data. Concrete creep may affect irradiation-induced cracking Irradiation-Assisted Alkali-Silica Reaction
- Irradiation-induced amorphization increases the dissolution rate of aggregates 1
QUESTIONS?